• Title/Summary/Keyword: heat transport

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Thermal Transport from an Aluminum Foam Heat Sink in a Confined Impinging Air Jet (국한 충돌공기제트에 의한 발포 알루미늄 방열기의 열전달 특성)

  • Hwang, Jun;Kim, Seo-Young;Kang, Byung-Ha
    • Transactions of the Korean Society of Mechanical Engineers B
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    • v.27 no.4
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    • pp.496-503
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    • 2003
  • An experimental study has been performed on thermal transport from an aluminum foam heat sink under a confined impinging air jet. Three kinds of aluminum foam heat sinks with 10, 20 and 40 PPI and a conventional pin-fin heat sink are tested in the present study. The jet Reynolds number is varied in the range of Re=667~5672 The effect of the confinement disk diameter and the distance between the confinement disk and the heater surface on the averaged Nusselt number is investigated in detail. The results are also compared with those of the unconfined impinging air jet. The critical distance, at which thermal performance shows a minimum compared to the unconfined jet impinging, will be described in terms of the Reynolds number and the pore density of the aluminum foam.

Molecular Dynamics Simulations for Transport Coefficients of Liquid Argon : New Approaches

  • Lee, Song-Hi;Park, Dong-Kue;Kang, Dae-Bok
    • Bulletin of the Korean Chemical Society
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    • v.24 no.2
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    • pp.178-182
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    • 2003
  • The stress and the heat-flux auto-correlation functions in the Green-Kubo formulas for shear viscosity and thermal conductivity have non-decaying long-time tails. This problem can be overcome by improving the statistical accuracy by N (number of particles) times, considering the stress and the heat-flux of the system as properties of each particle. The mean square stress and the heat-flux displacements in the Einstein formulas for shear viscosity and thermal conductivity are non linear functions of time since the quantities in the mean square stress and the heat-flux displacements are not continuous under periodic boundary conditions. An alternative to these quantities is to integrate the stress and the heat-flux with respect to time, but the resulting mean square stress and heat-flux displacements are still not linear versus time. This problem can be also overcome by improving the statistical accuracy. The results for transport coefficients of liquid argon obtained are discussed.

An Investigation on Friction Factors and Heat Transfer Coefficients in a Rectangular Duct with Surface Roughness

  • Ahn, Soo-Whan;Son, Kang-Pil
    • Journal of Mechanical Science and Technology
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    • v.16 no.4
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    • pp.549-556
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    • 2002
  • An investigation on the fully developed heat transfer and friction factor characteristics has been made in rectangular ducts with one-side roughened by five different shapes. The effects of rib shape geometries as well as Reynolds numbers are examined. The rib height-to-duct hydraulic diameter, pitch-to-height ratio, and aspect ratio of channel width to height are fixed at e/De=0.0476, P/e=8, and W/H=2.33, respectively. To understand the characteristics of heat transfer enhancements, the friction factors are also measured. The data indicates that the triangular type rib has a substantially higher heat transfer performance than any other ones.

Study on Urban Temperature Prediction Method Using Lagrangian Particle Dispersion Model (라그랑지안 입자모델을 활용한 도시기온 예측기법의 연구)

  • Kim, Seogcheol;Yun, Jeongim
    • Journal of Korean Society for Atmospheric Environment
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    • v.33 no.1
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    • pp.45-53
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    • 2017
  • A high resolution model is proposed for calculating the temperature field of a large city, based upon a Lagrangian particle model. Utilizing the analogy between the heat and mass transport phenomena in turbulent flows, a Lagrangian particle model, originally developed for air pollutant dispersion problems, is adapted for simulating heat transport. In the model conceptual heat particles are released into the atmosphere from the heat sources and move along with the turbulent winds in accordance with the Markov process. The potential temperature assumed to be conserved along with heat particles serves as a tag, so the temperature fields can be deduced from the distribution of particles. The wind fields are constructed from a diagnostic meteorology model incorporating a morphological model designed for building flows. Test run shows the robustness of the modeling system.

Mass Transfer and Heat Transfer Characteristics of PEM fuel cell by Permeability of GDL (GDL Permeability에 따른 고분자 전해질 연료전지의 물질전달 및 열전달 특성에 관한 연구)

  • Han, Sang-Seok;Lee, Pil-Hyong;Park, Chang-Soo;Lee, Jae-Young;Hwang, Sang-Soon
    • Proceedings of the KSME Conference
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    • 2008.11b
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    • pp.2822-2827
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    • 2008
  • Among the main components of PEM fuel cell, the functions of GDL are to transport reactants from the channel to the catalyst and remove reaction products from the catalyst and transport heat from the catalyst to the channels in the flow filed plate. Permeability of GDL is known to make it possible to enhance the gas transport through GDL, devoting to get better performance. In this paper, three dimensional numerical simulation of the fuel cell by the permeability of GDL is presented by using a FLUENT modified to include the electrochemical behavior. Results show that as permeability is higher than $10^{-12}m^2$, gradients of temperature distribution, oxygen molar concentration and current density distribution in MEA were decreased. Although heat generation was increased as high permeability, MEA's temperature was lower than the low permeability of GDL. This seems because that convection was higher affects in mass and heat transfer process than diffusion as permeability of GDL is increases.

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Abnormal Operation Analysis of the Wolsong 2,3,4 Heat Transport System (월성 2,3,4호기 열수송계통의 비정상 운전 해석)

  • Shin, J.C.
    • Journal of Energy Engineering
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    • v.25 no.1
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    • pp.15-22
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    • 2016
  • The heat transport system transients of Wolsong 2,3,4 nuclear power plants were analysed during abnormal operating conditions. The compliance with requirements of AECB Regulatory Document R-77 for CANDU reactor was estimated. The analysis results showed that for each postulated accident the peak pressure values in the reactor headers are within the acceptance criteria given in ASME code requirements. The effect of LRV that is one of the overpressure protection device was very minor.

Structural Concept Design of KALIMER-600 Sodium Cooled Fast Reactor (소듐냉각 고속로 KALIMER-600 원자로 구조 개념설계)

  • Lee, Jae-Han;Park, Chang-Gyu;Kim, Jong-Bum;Koo, Gyeong-Hoi
    • Proceedings of the KSME Conference
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    • 2007.05a
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    • pp.285-290
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    • 2007
  • KALIMER-600 is a sodium cooled fast reactor with a fast spectrum neutron reactor core. The NSSS design has three heat transport systems of a PHTS (Primary Heat Transport System), a IHTS (Intermediate Heat Transport System) and a SGS (Steam Generation System). PHTS is a pool type and has a large amount of sodium in the pool. The mechanical design targets are maintaining the enough structural integrity for a seismic load of SSE 0.3g and the thermal and mechanical loads by the high temperature environments and an economical competitiveness when compared with other reactor types.

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Development of a Multi-Physics Model of Polymer Electrolyte Membrane Fuel Cell Using Aspen Custom Modeler (Aspen Custom Modeler를 이용한 고분자전해질 연료전지 다중 물리 모델 개발)

  • SON, HYEYOUNG;HAN, JAESU;YU, SANGSEOK
    • Transactions of the Korean hydrogen and new energy society
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    • v.32 no.6
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    • pp.489-496
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    • 2021
  • The performandce of polymer electrolyte membrane fuel cell depends on the effective management of heat and product water by the electrochemical reaction. This study is designed to investigate the parametric change of heat management along the channel of polymer electrolyte membrane. The model was developed by an aspen custom modeler that it can solve differential equation with distretization model. The model can simulate water transport through the membrane electrolyte that is coupled with heat generation. In order to verify the model, it is compared with the experimental data. The water transport behavior is then evaluated with the simulation model.

Effects of the Mass of Working Fluid on the Thermal Performance of Heat Pipe with Axial Grooves (그루브형 히트파이프에서 작동유체량이 히트파이프 성능에 미치는 영향)

  • Suh, Jeong-Se;Park, Young-Jun
    • Korean Journal of Air-Conditioning and Refrigeration Engineering
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    • v.15 no.1
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    • pp.1-8
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    • 2003
  • An analytical and experimental study of the thermal performance of axial heat pipe with axial groove is conducted to determine the optimal mass of working fluid for the maximum heat transport capacity of heat pipe with axial grooves. Generally, the mass of working fluid has been fully charged by considering only a geometrical shape of axial grooves embedded in a heat pipe. When the heat pipe is operated in a steady state, the meniscus re-cession phenomena of working fluid is occurred in the evaporator region. In this work, the optimal mass of working fluid was obtained from the axial variation of capillary pressure, the radius of curvature and wetting angle of meniscus of liquid-vapor interface. Experimental results were also obtained by varying the mass of working fluid within a heat pipe, and presented for the maximum heat transport capacity corresponding to the operating temperature and the elevation of heat pipe. Finally, the analytical results of the optimal mass of working fluid were compared with those of the experimental mass of working fluid.

STEAM GENERATOR TUBE INTEGRITY ANALYSIS OF A TOTAL LOSS OF ALL HEAT SINKS ACCIDENT FOR WOLSONG NPP UNIT 1

  • Lim, Heok-Soon;Song, Tae-Young;Chi, Moon-Goo;Kim, Seoung-Rae
    • Nuclear Engineering and Technology
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    • v.46 no.1
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    • pp.39-46
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    • 2014
  • A total loss of all heat sinks is considered a severe accident with a low probability of occurrence. Following a total loss of all heat sinks, the degasser/condenser relief valves (DCRV) become the sole means available for the depressurization of the primary heat transport system. If a nuclear power plant has a total loss of heat sinks accident, high-temperature steam and differential pressure between the primary heat transport system (PHTS) and the steam generator (SG) secondary side can cause a SG tube creep rupture. To protect the PHTS during a total loss of all heat sinks accident, a sufficient depressurization capability of the degasser/condenser relief valve and the SG tube integrity is very important. Therefore, an accurate estimation of the discharge through these valves is necessary to assess the impact of the PHTS overprotection and the SG tube integrity of the primary circuit. This paper describes the analysis of DCRV discharge capacity and the SG tube integrity under a total loss of all heat sink using the CATHENA code. It was found that the DCRV's discharge capacity is enough to protect the overpressure in the PHTS, and the SG tube integrity is maintained in a total loss of all heat accident.